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Machine learning informed visco-plastic model for the cyclic relaxation of 316H stainless steel at 550 °C 期刊论文
INTERNATIONAL JOURNAL OF PLASTICITY, 2023, 卷号: 170, 页码: 23
作者:  Du R(杜柔);  Song HX(宋恒旭);  Gao, Fuhai;  Mo, Yafei;  Yan, Ziming
收藏  |  浏览/下载：5/0  |  提交时间：2024/02/19
Numerical evaluation of hypothetical core disruptive accident in full- scale model of sodium-cooled fast reactor 期刊论文
NUCLEAR ENGINEERING AND TECHNOLOGY, 6, 2022, 卷号: 54, 页码: 2120
作者:  Guo ZH(郭志鸿);  Chen XD(陈晓东);  Hu GQ(胡国庆)
收藏  |  浏览/下载：14/0  |  提交时间：2022/10/23
Effect of Clearance of Rotor-Stator Cascade on Pressure Fluctuation in Secondary Circuit Coolant Pump for Sodium-Cooled Fast Reactor 期刊论文
Hedongli Gongcheng/Nuclear Power Engineering, 2020, 卷号: 41, 期号: 1, 页码: 127-133
作者:  Yang, Congxin;  Liu, Man;  Wang, Xiuyong;  Yu, Hongchang;  Niu, Hongjun
收藏  |  浏览/下载：11/0  |  提交时间：2020/11/14
Friction and Wear Behavior of CrN Coating on 316L Stainless Steel in Liquid Sodium at Elevated Temperature 期刊论文
TRIBOLOGY INTERNATIONAL, 2020, 卷号: 143
作者:  Chen, Yanjun;  Wang, Shunhua;  Ha, Yu;  Pu, Jibin;  Jiang, Xin
收藏  |  浏览/下载：12/0  |  提交时间：2020/12/16
Sensitivity analysis and similarity evaluation of sodium-cooled fast reactor in large size 期刊论文
Annals of Nuclear Energy, 2019, 卷号: 125, 页码: 283-290
作者:  Zheng, Youqi;  Qiao, Liang;  Wan, Chenghui;  Cao, Liangzhi;  Liu, Yong
收藏  |  浏览/下载：13/0  |  提交时间：2019/11/19
Numerical study on thermal deformation behaviors of the single subassembly in sodium-cooled fast reactors based on Euler-Bernoulli beam theory 期刊论文
NUCLEAR ENGINEERING AND DESIGN, 2019, 卷号: 345, 页码: 28-39
作者:  Ma, Zhenhui;  Ma, Zehua;  Wu, Yingwei;  Wang, Mingjun;  Su, G. H.
收藏  |  浏览/下载：146/0  |  提交时间：2019/11/19
Numerical approach to study the thermal-hydraulic characteristics of Reactor Vessel Cooling system in sodium-cooled fast reactors 期刊论文
Progress in Nuclear Energy, 2019, 卷号: 110, 页码: 213-223
作者:  Song, Ping;  Zhang, Dalin;  Feng, Tangtao;  Wang, Shibao;  Chen, Jing
收藏  |  浏览/下载：31/0  |  提交时间：2019/11/19
Thermal-hydraulic analysis code development for sodium heated once-through steam generator 期刊论文
Annals of Nuclear Energy, 2019, 卷号: 127, 页码: 385-394
作者:  Xu, Rongshuan;  Zhang, Dalin;  Tian, Wenxi;  Qiu, Suizheng;  Su, G.H.
收藏  |  浏览/下载：11/0  |  提交时间：2019/11/19
A best-estimated correlation for prediction of nucleation radius in sodium boiling 期刊论文
NUCLEAR ENGINEERING AND DESIGN, 2019, 卷号: 345, 页码: 40-46
作者:  Ma, Zaiyong;  Qiu, Suizheng;  Zhang, Luteng;  Bu, Shanshan;  Sun, Wan
收藏  |  浏览/下载：2/0  |  提交时间：2019/11/19
Numerical approach to study the thermal-hydraulic characteristics of Reactor Vessel Cooling system in sodium-cooled fast reactors 期刊论文
Progress in Nuclear Energy, 2019, 卷号: Vol.110, 页码: 213-223
作者:  Song, Ping;  Zhang, Dalin;  Feng, Tangtao;  Wang, Shibao;  Chen, Jing
收藏  |  浏览/下载：7/0  |  提交时间：2019/12/13

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